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Major refactor to include cross sections at multiple temperatures within the
Nuclide and SAlphaData derived types.
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4448d17ee1
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121 changed files with 1670 additions and 2213 deletions
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@ -33,7 +33,6 @@ fuel.add_nuclide(u235, 1.)
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([moderator, fuel])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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@ -38,7 +38,6 @@ moderator.add_s_alpha_beta('c_H_in_H2O')
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([fuel1, fuel2, moderator])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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@ -37,7 +37,6 @@ iron.add_nuclide(fe56, 1.)
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([moderator, fuel, iron])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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@ -32,7 +32,6 @@ moderator.add_s_alpha_beta('c_H_in_H2O')
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials((moderator, fuel))
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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@ -32,7 +32,6 @@ moderator.add_s_alpha_beta('c_H_in_H2O')
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([moderator, fuel])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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@ -102,7 +102,6 @@ borated_water.add_s_alpha_beta('c_H_in_H2O')
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([uo2, helium, zircaloy, borated_water])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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@ -19,7 +19,7 @@ groups = openmc.mgxs.EnergyGroups(group_edges=[1E-11, 0.0635E-6, 10.0E-6,
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1.0E-4, 1.0E-3, 0.5, 1.0, 20.0])
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# Instantiate the 7-group (C5G7) cross section data
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uo2_xsdata = openmc.XSdata('UO2.300K', groups)
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uo2_xsdata = openmc.XSdata('UO2', groups)
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uo2_xsdata.order = 0
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uo2_xsdata.total = [0.1779492, 0.3298048, 0.4803882, 0.5543674,
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0.3118013, 0.3951678, 0.5644058]
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@ -41,7 +41,7 @@ uo2_xsdata.nu_fission = [2.005998E-02, 2.027303E-03, 1.570599E-02,
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uo2_xsdata.chi = [5.8791E-01, 4.1176E-01, 3.3906E-04, 1.1761E-07,
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0.0000E+00, 0.0000E+00, 0.0000E+00]
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h2o_xsdata = openmc.XSdata('LWTR.300K', groups)
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h2o_xsdata = openmc.XSdata('LWTR', groups)
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h2o_xsdata.order = 0
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h2o_xsdata.total = [0.15920605, 0.412969593, 0.59030986, 0.58435,
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0.718, 1.2544497, 2.650379]
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@ -66,8 +66,8 @@ mg_cross_sections_file.export_to_xml()
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###############################################################################
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# Instantiate some Macroscopic Data
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uo2_data = openmc.Macroscopic('UO2', '300K')
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h2o_data = openmc.Macroscopic('LWTR', '300K')
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uo2_data = openmc.Macroscopic('UO2')
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h2o_data = openmc.Macroscopic('LWTR')
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# Instantiate some Materials and register the appropriate Macroscopic objects
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uo2 = openmc.Material(material_id=1, name='UO2 fuel')
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@ -80,7 +80,6 @@ water.add_macroscopic(h2o_data)
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([uo2, water])
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materials_file.default_xs = '300K'
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materials_file.export_to_xml()
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@ -25,7 +25,6 @@ fuel.add_nuclide(u235, 1.)
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([fuel])
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materials_file.default_temperature = '294K'
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materials_file.export_to_xml()
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